ML20039B898
| ML20039B898 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 11/24/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20039B889 | List: |
| References | |
| NUDOCS 8112280027 | |
| Download: ML20039B898 (2) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
- M%
g({k UNITED STATES g
NUCLEAR REGULATORY COMMISSION y
3,'
A E WASHINGTON, D. C. 20555 hs SAFETY EVALUATION BY THE ~0FFICE OF NUCLEAR ~ REACTOR REGULATION RELATED TO AMENDMENT N0. S 9 TO FACILITY OPERATING LICENSE'NO. 'NPF-1 PORTLAND GENERAL ELECTRIC COMPANY
~
EECITYOFEUGENE, OREGON PACIFIC POWER ~AND LIGHT COMPANY TROJAN NUCLEAR PLANT DOCKET NO. 50-344 Introduction By letter dated October 8,1981, Portland General Electric Company, et al.,
requested an amendment to Facility Operating License No. NPF-1 for operaticn of the Trojan Nuclear Plant in Columbia County, Oregon. The proposed changes relate to operability requirements for fire detection instruments and' revised procedures for inspection of fire hose stations in inaccessible areas of the
%;p,lant while it is in operation.
Discussion and Evaluation 1.
Fire Detection Instruments by Fire Zones The present Technical Specifications (Ta'ble 3.3-10) identify the minimum number of fire detection instruments required to be operable for each safety-related space or room as a total number of detectors for that space or rcom without regard to the separate fire zones within that space. Th.e licensee proposes to identify (within each space) the minimum number of fire detectors required to be operable for each fire zone, so that each fire zone within each space or room has required fire detection..This represents an improvement over the present requirements because it assures that each fire zone has fire detection coverage, as well as each space or room. We, therefore, find this change acceptable. The change is also consistent with NUREG-0452, Rev. 3,
- " Standard Technical Specifications for Westinghouse Pressurized Water Reactors".
2.
Additional Spaces - Fire Detection Instruments The licensee proposes to add operability requirements for fire detection instru-ments for eight new areas consistent with the change discussed above. These areas are:
auxiliary feedwater pump rooms residual heat removal pump rooms service water pump area service water booster pump area centrifugal charging pump rooms emergency diesel generator rooms component cooling water pump area safety injection pump rooms 8112280027 811124
PDR ADOCK 05000344 P
pop
Trojan The addition of these instruments (24 total) is consistent with PGE-1012,
" Trojan Nuclear Plant Fire Protection Review" and NRC's review of fire pro-tection for the Trojan facility. Adding these instruments will require these instruments to be maintained in an operable status and tested periodically consistent with the reliance placed on them in the fire protection evaluation.
We therefore find this change acceptable.
3.
Revised Inspection for Inaccessible Fire Hose Stations The present Technical Specifications require each fire hose station identified in the Technical Specifications to be visually inspected at least once per 31 days to assure all required equipment is at the stations. The licensee propo us to modify this requirement for fire hose stations that are inaccessible during plant operation, i.e., those that are in the containment building. The licensee proposes to inspect these at each cold shutdown exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in duration unless an inspection has been performed in the previous 31 days. Since the fire hose stations in containment are inaccessible during plant operation, it is unlikely that they would be disturbed since personnel do rot routinely enter the containment. The, radiation exposure which is incurred during such inspections is unwarranted. This proposed change is. consistent with, and somewhat more stringent than, the Standard Technical Specifications (NUREQ-
% 0,452, Rev. 3). We therefore find the proposed change acceptable.
Environmental Consideraticn We have determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, we have further concluded that the amendment invcives an action which is insignificant from the standpoint of environmental impact and, pursuant to 10 CFR 51.5(d)(4), that an environmental impact statement or negative declaration and environ-mental impact appraisal need not be prepared in connection with the issuance of this amendment.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the probability or consequences of acciGents previously considered and does not involve a significant decrease in a safety margin, the amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation im the proposed manner,/and (3) such activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.
Date: November 24, 1981
_ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _